Criticality validation of SuperMC with ICSBEP

Abstract Monte Carlo transport codes are extensively used in neutronic analysis, especially in criticality safety analysis and shielding analysis. Super Monte Carlo Simulation Program for Nuclear and Radiation Process (SuperMC) is a CAD based Monte Carlo program for integrated simulation of nuclear systems. The aim of this paper was to show the capability of SuperMC on criticality calculation with different models. In this study 119 representative benchmarks from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP) were used for validating the code. All the benchmark models and input files were built and completed by employing the models’ conversion and construction function of SuperMC. The results showed that there was a good agreement between SuperMC and experimental data, and the discrepancies were mainly included in the statistical uncertainty.

[1]  Yican Wu,et al.  CAD-based interface programs for fusion neutron transport simulation , 2009 .

[2]  Jean-Christophe Sublet,et al.  ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks and Reactor Experiments , 2011 .

[3]  Bin Wu,et al.  A low aspect ratio tokamak transmutation system , 2000 .

[4]  Jun Zou,et al.  Production and testing of HENDL-2.1/CG coarse-group cross-section library based on ENDF/B-VII.0 , 2010 .

[5]  J. Leppänen.  Development of a New Monte Carlo reactor physics code , 2007 .

[6]  Fds Team,et al.  A fusion-driven subcritical system concept based on viable technologies , 2011 .

[7]  Van Der Marck,et al.  Benchmarking ENDF/B-VII.1, JENDL-4.0 and JEFF-3.1 , 2012 .

[8]  Yican Wu,et al.  Conceptual design of the China fusion power plant FDS-II , 2008 .

[9]  Jun Zou,et al.  Development and testing of multigroup library with correction of self-shielding effects in fusion–fission hybrid reactor , 2010 .

[10]  Yican Wu,et al.  Conceptual design and testing strategy of a dual functional lithium–lead test blanket module in ITER and EAST , 2007 .

[11]  Huaichuan Hu,et al.  Benchmarking of MCAM 4.0 with the ITER 3D model , 2007 .

[12]  Fds Team,et al.  Fusion-based hydrogen production reactor and its material selection , 2009 .

[13]  Ulrich Fischer,et al.  A discrete ordinates nodal method for one-dimensional neutron transport calculation in curvilinear geometries , 1999 .

[14]  Forrest B. Brown,et al.  An expanded criticality validation suite for MCNP , 2011 .

[16]  Huaqing Zheng,et al.  CAD-based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC , 2014, ICS 2014.

[17]  Hyung Jin Shim,et al.  MCCARD : MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS , 2012 .

[18]  Jean-Charles Jaboulay,et al.  TRIPOLI-4® Monte Carlo code ITER A-lite neutronic model validation , 2014 .

[19]  Huaqing Zheng,et al.  Benchmarking of CAD-based SuperMC with ITER benchmark model , 2014 .

[20]  J. P. Qian,et al.  The fusion-driven hybrid system and its material selection , 2002 .

[21]  Russell Feder,et al.  State-of-the-art 3-D radiation transport methods for fusion energy systems , 2008 .